TED-AJ03-625 THE PENNSYLVANIA STATE UNIVERSITY AND U. S. NUCLEAR REGULATORY COMMISSION ROD BUNDLE HEAT TRANSFER FACILITY

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概要

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• Best-Estimate thermal-hydraulic methods are being used to evaluate the accident mitigation performance of the Emergency Core cooling Systems (ECCS) which are presently installed on Operating Nuclear Power Plants. The use of Best-Estimate methods indicate that there is conservatism in the calculated performance of the safety systems such that the plant power and or the peaking factors can be increased without a loss of safety margin. To verify the performance of the ECCS, the US NRC is upgrading its safety analysis computer code which is used for audit calculations. Toimprove the computer code and its associated models requires additional and more detailed experimental data. The rod Bundle Heat transfer Facility, which has been constructed at the Penn State University at University Park, PA has been design to provide the needed and detailed experimental data. Experiments are being performed over the full range of reflood conditions and such that the full range of the boiling curve will be investigated for a wide range of fluid conditions. The emphasis will be on examining, in detail, the dispersed for heat transfer regime which is the limiting heat transfer situation for the calculated Loss of Coolant Accident (LOCA). The test facility has been constructed and new and additional instrumentation is being used to provide more detailed data. In addition. the facility uses prototypical mixing vane spacer grids. It has been observed that the spacer grids have a first order effect on improving the heat transfer in the dispersed flow film boiling regime. The resulting measured heat transfer coefficients downstream of the grids are much higher and the degree of vapor superheat is significantly reduced. It is believed that the spacers act to shatter the entrained liquid

• 一般社団法人日本機械学会の論文

著者

• Cheung Fan

  Mechanical And Nuclear Engineering The Pennsylvania State University

• Hochreiter Lawrence

  Mechanical And Nuclear Engineering The Pennsylvania State University

• Kelly Joseph

  Office Of Research Us Nuclear Regulatory Commission

• Rosal Enrique

  Applied Research Laboratory The Pennsylvania State University

• Lin Thomas

  Applied Research Laboratory The Pennsylvania State University

• McClellan Ian

  Applied Research Laboratory The Pennsylvania State University

• Rhee Gene

  Office of Research US Nuclear Regulatory Commission

• Bajorek Stephen

  Office of Research US Nuclear Regulatory Commission

関連論文

• TED-AJ03-625 THE PENNSYLVANIA STATE UNIVERSITY AND U. S. NUCLEAR REGULATORY COMMISSION ROD BUNDLE HEAT TRANSFER FACILITY

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